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Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3
Lind, T., Pellegrini, M., Herranz, L. E., Sonnenkalb, M., Nishi, Y., Tamaki, H., … Sevon, T. (2021). Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3. Nuclear Engineering and Design, 376, 111138 (12 pp.). https://doi.org/10.1016/j.nucengdes.2021.111138
Analysis for the ARIANE GU1 sample: nuclide inventory and decay heat
Rochman, D., Vasiliev, A., Ferroukhi, H., & Hursin, M. (2021). Analysis for the ARIANE GU1 sample: nuclide inventory and decay heat. Annals of Nuclear Energy, 160, 108359 (19 pp.). https://doi.org/10.1016/j.anucene.2021.108359
Computed tomography combined with a material decomposition technique using a compact deuterium-deuterium (D-D) fast neutron generator
Soubelet, B., Adams, R., & Prasser, H. M. (2021). Computed tomography combined with a material decomposition technique using a compact deuterium-deuterium (D-D) fast neutron generator. Radiation Physics and Chemistry, 181, 109296 (11 pp.). https://doi.org/10.1016/j.radphyschem.2020.109296
Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release
Stuckert, J., Steinbrueck, M., Kalilainen, J., Lind, T., & Birchley, J. (2021). Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release. Nuclear Engineering and Design, 379, 111267 (11 pp.). https://doi.org/10.1016/j.nucengdes.2021.111267
Studies of reactor noise response to vibrations of reactor internals and thermal-hydraulic fluctuations in PWRs
Verma, V., Chionis, D., Dokhane, A., & Ferroukhi, H. (2021). Studies of reactor noise response to vibrations of reactor internals and thermal-hydraulic fluctuations in PWRs. Annals of Nuclear Energy, 157, 108212 (19 pp.). https://doi.org/10.1016/j.anucene.2021.108212
Measurement of the gas velocity in a water-air mixture in CROCUS using neutron noise techniques
Hursin, M., Pakari, O., Perret, G., Frajtag, P., Lamirand, V., Pázsit, I., … Pautz, A. (2020). Measurement of the gas velocity in a water-air mixture in CROCUS using neutron noise techniques. Nuclear Technology, 206(10), 1566-1583. https://doi.org/10.1080/00295450.2019.1701906
Validation of axial void profile measured by neutron noise techniques in CROCUS
Hursin, M., Pakari, O., Perret, G., Frajtag, P., Lamirand, V., Pázsit, I., … Pautz, A. (2020). Validation of axial void profile measured by neutron noise techniques in CROCUS. In Proceedings of the PHYSOR 2020 (p. 1173 (8 pp.). Nuclear Energy Group.
Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor
Kim, W., Hursin, M., Pautz, A., Vincent, L., Pavel, F., & Lee, D. (2020). Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor. Annals of Nuclear Energy, 136, 107034 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107034
Dry storage modeling activities at PSI: implementation and testing of a creep model for dry storage
Konarski, P., Cozzo, C., Khvostov, G., & Ferroukhi, H. (2020). Dry storage modeling activities at PSI: implementation and testing of a creep model for dry storage. Kerntechnik, 85(6), 419-425. https://doi.org/10.3139/124.200072
Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX
Lamirand, V., Rais, A., Pakari, O., Hursin, M., Laureau, A., Polhus, J., … Pautz, A. (2020). Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX. In Proceedings of the PHYSOR 2020 (p. 1573 (9 pp.). Nuclear Energy Group.
Uncertainty propagation based on correlated sampling technique for nuclear data applications
Laureau, A., Lamirand, V., Rochman, D., & Pautz, A. (2020). Uncertainty propagation based on correlated sampling technique for nuclear data applications. EPJ Nuclear Sciences and Technologies, 6, 8 (9 pp.). https://doi.org/10.1051/epjn/2020003
Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor
Laureau, A., Lamirand, V., Rochman, D., & Pautz, A. (2020). Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor. EPJ Nuclear Sciences and Technologies, 6, 9 (8 pp.). https://doi.org/10.1051/epjn/2020004
CORE SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements
Mylonakis, A. G., Demazière, C., Vinai, P., Lamirand, V., Rais, A., Pakari, O., … Pautz, A. (2020). CORE SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements. In Proceedings of the PHYSOR 2020 (p. 1207 (9 pp.). Nuclear Energy Group.
Statistical burnup distribution of moving pebbles in the HTR-PM reactor
Vitullo, F., Krepel, J., Kalilainen, J., Prasser, H. M., & Pautz, A. (2020). Statistical burnup distribution of moving pebbles in the HTR-PM reactor. Journal of Nuclear Engineering and Radiation Science, 6(2), 021108 (14 pp.). https://doi.org/10.1115/1.4044910
Measurement of the gas velocity in a water-air mixture in crocus by neutron noise technique
Hursin, M., Pakari, O., Perret, G., Frajtag, P., Lamirand, V., Pázsit, I., … Pautz, A. (2019). Measurement of the gas velocity in a water-air mixture in crocus by neutron noise technique (p. (8 pp.). Presented at the International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). American Nuclear Society.
Thermal analysis, design, and testing of a rotating beam target for a compact D-D fast neutron generator
Kromer, H., Adams, R., Soubelet, B., Zboray, R., & Prasser, H. M. (2019). Thermal analysis, design, and testing of a rotating beam target for a compact D-D fast neutron generator. Applied Radiation and Isotopes, 145, 47-54. https://doi.org/10.1016/j.apradiso.2018.12.009
An experimental programme optimized with uncertainty propagation: PETALE in the CROCUS reactor
Lamirand, V., Laureau, A., Rochman, D., Perret, G., Gruel, A., Leconte, P., … Pautz, A. (2019). An experimental programme optimized with uncertainty propagation: PETALE in the CROCUS reactor. In O. Serot & A. Chebboubi (Eds.), EPJ web of conferences: Vol. 211. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications (p. 03003 (5 pp.). https://doi.org/10.1051/epjconf/201921103003
Total Monte Carlo acceleration for the PETALE experimental programme in the CROCUS reactor
Laureau, A., Lamirand, V., Rochman, D., & Pautz, A. (2019). Total Monte Carlo acceleration for the PETALE experimental programme in the CROCUS reactor. In O. Serot & A. Chebboubi (Eds.), EPJ web of conferences: Vol. 211. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications (p. 03002 (5 pp.). https://doi.org/10.1051/epjconf/201921103002
Evaluation of the PAR mitigation system in Swiss PWR containment using the GOTHIC code
Papini, D., Andreani, M., Steiner, P., Ničeno, B., Klügel, J. U., & Prasser, H. M. (2019). Evaluation of the PAR mitigation system in Swiss PWR containment using the GOTHIC code. Nuclear Technology, 205(1-2), 153-173. https://doi.org/10.1080/00295450.2018.1505356
Global sensitivity and registration strategy for temperature profile of reflood experiment simulations
Perret, G., Wicaksono, D., Clifford, I. D., & Ferroukhi, H. (2019). Global sensitivity and registration strategy for temperature profile of reflood experiment simulations. Nuclear Technology, 205(12), 1638-1651. https://doi.org/10.1080/00295450.2019.1591154
 

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